ML19305D096

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Response to AA Aamodt 800225 Fourth Set of Interrogatories Re Restart Proceeding.Includes Info Re Training in Basic Heat Transfer,Fluid Flow & Thermodynamics.Supporting Documentation & Gf Trowbridge 800331 Ltr Encl
ML19305D096
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 03/31/1980
From: Trowbridge G
METROPOLITAN EDISON CO., SHAW, PITTMAN, POTTS & TROWBRIDGE
To: Aamodt A
AFFILIATION NOT ASSIGNED
Shared Package
ML19305D049 List:
References
NUDOCS 8004140057
Download: ML19305D096 (36)


Text

h* LIC 3/31/80 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )

)

METROPOLITAN EDISON COMPANY ) Docket No. 50-289

) (Restart)

(Three Mile Island Nuclear )

Station, Unit No. 1) )

LICENSEE'S RESPONSE TO THE FOURTH SET [ SIC; FIFTH SET) OF INTERROGATORIES FROM MARJORIE M. AAMODT (DATED FEBRUARY 25, 1980)

INTERROGATORY NO. 1 Do you plan to increase the amount of basic engineering and physics training in thermal hydraulics for operators and senior operators?

(a) Provide description of course material and time allowed to master.

(b) Provide names and background (education and experience) of instructors.

RESPONSE

Initially, training in basic heat transfer, fluid flow, and thermo dynamics is being increased through the Operator Acceleiated -

Retraining Program (OARP) (see Restart Report, Section 6), which includes 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> of instruction in this subject. The principal instructor is Chester F. Kupiec, Jr. A copy of Mr. Kupiec's resume is attached. Information on the OARP lesson plans will be placed in Licensee's Discovery Reading Room. Insofar as the 8 0 0 414 0CHE5I

" time allowed to master" this material, operators are first examined for retention of the lessons upon completion of instruction; and are thereafter orally examined upon completion of instruction of all the material in the OARP. In addition, operators will be examined after the OARP and prior to restart by an independent consultant from Personnel Qualifications Serv-ices (Frank Kelly). See Response to Interrogatory No. 4.

Licensee also plans to increase instruction in this subject in its Operator Training Program (OTP). Course content has not yet been finalized; however, it will at a minimum include instruction in basic heat transfer, fluid flow and thermo dynamics as contained in the OARP. Further, the OTP standards are under review by two special review committees, each of which will be making recommen-dations for improvements in the OTP standards.

INTERROGATORY NO. 2 What instruction in basic engineering and physics of thermal hydraulics was given to operators and senior operators prior to TMI-2 accident? ,

(a) Provide descriptf.on of course material and time allowed to master.

(b) Provide names and backgrounds (education and experience) of instructors.

RESPONSE

Training in basic heat transfer, fluid flow and thermo dynamics, as generally described in the Unit 1 FSAR, Section 12, was given to Operators and Senior Reactor Operators before obtaining cold licenses prior to Unit 1 startup. Subsequent

classes received limited specific formal training in the subject: ,

however, principles of basic heat transfer, fluid flow and thermo l dynamics did form a part of the instruction given in reactor ,

t operations, turbine cycle operations and heat exchange operations.

Licensee's records do not indicate the names of instructors l who gave cold license instruction in this subject. Dennis J. f l

Boltz, Nelson D. Brown and Richard W. Zechman instructed in l

reactor operations, turbine cycle operations or heat exchange {

operations prior to the TMI-2 accident. The resumes of these  !

i training department personnel are attached. l i

, INTERROGATORY NO. 3 I

! i If the answer to #1 is "yes," give reason why. [

(a) Relate to TMI'-2 accident.

(b) Had a deficiency in this kind of training ever been perceived prior to TMI-2 accident studies?

(c) Explain.

RESPONSE

Licensee believes that the intensified training in basic heat transfer, fluid flow, and thermo dynamics, discussed in the Response to Interrogatory No. 1 will assist the operator in ,

t better diagnosing and responding to transients such as those which occurred during the TMI-2 accident.

Portions of the Operator Training Program relating to this subject which were conducted at TMI were based on experience gained in operations and training at both military and commercial nuclear power plants, and followed generally accepted industry standards

in effect prior to the TMI-2 accident. Licensee considered these training standards to be adequate.

INTERROGATORY NO. 4 Provide a copy of tests proposed to be used to test retention of course material referred to in Question 1.a.

(a) How will tests be graded?

(b) Who will grade tests?

(1) Provide names and background.

(c) What will be considered a passing grade?

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(d) What grade will indicate need for retraining?

(1) Will any other factors be considered in eligibility for retraining?

(e) What grade will cause dismissal from program? i (1) Will any other factors be considered in dismissal?

RESPONSE

As described in the Restart Report, Section 6, an examination is under preparation by Frank Kelly, an independent consultant t

retained by Licensee to administer an audit examination of the Licensed Reactor Operators and Senior Reactor Operators. To preserve the validity of the test, it will not be available until after they are administered. See Licensee's March 14, 1980 objection to Aamodt Interrogatory Nc, 4.

(a) The test will contain essay questions and will be graded based on the specific objectives of the questions. -

(b) See attached resume.

(c) The passing grade criteria for the examination are contained in the Licensee's Restart Report, Appendix A, Response to Question 47.

(d) Retraining criteria are contained in the reference cited in c. above. Weak areas, as defined in the audit, will t

be reviewed to determine retraining requirements.

(e) The criteria for Licensee action for unsatisfactory grades on the audit examination are contained in Section 6.6 of the Restart Report.

INTERROGATORY NO. S Who constructed (or will construct) tests requested in #47 (a) Provide the .9me 'of company or individuals and background.

l (b) Were any principles of test construction used' to insure reliability o:5 test to predict performance? Explain.

RESPONSE

(a) See Response to Interrogatory No. 4.

(b) The tests are being constructed in accordance with NRC requirements contained in NUREG-0094. Without a defin-ition of what this interrogatory means by " principles of test construction used to insure reliability of test to predict performance" Licensee is unable to respond further to this interrogatory.

INTERROGATORY NO. 6 For each position in the control room, provide the following for pre-TMI-2 accident:

(a) Educational background required.

(b) Experience required.

(c) Training required including course name, descrip-tion of material covered, length of time for training, length of average training day.

(d) Tests required for each course, indicating passing grade, retraining grade and dismissal grade.

RESPONSE

Prior to the TMI-2 accident, minimum education and experi-ence standards for Licensee's control room personnel were based on minimum standards contained in American National Standard, ANSI, N18.1-1971, Selection and Training of Nuclear Power Plant Personnel. A copy of the ANSI standard will be placed in Licensee's Discovery Reading Room.

Training and test requirements for control room operators in effect prior to the TMI-2 accident were contained in Licen-see's Auxiliary Operator C Program, Auxiliary Operator B Pro-gram, Replacement Con' rol Room Operator Program and Shift Fore-man and Shift Supervisor Programs. A description of these pro-grams will be placed in Licensee's Discovery Reading Room.

INTERROGATORY NO. 7 Same as #6 for post-TMI-2 accident.

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i RESPONSE  :

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The minimum education and experience requirement and the l l

4 basic training course and tests are currently the same as  ;

described in Licensee's Response to Interrogatory No. 6. These  ;

i requirements are under review by two special review committees t

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as described in Licensee's Response to Interrogatory No.1. '

In addition, Licensee is conducting an Operator Accelerated Re- j training Program, as described in the TMI-l Restart Report,  ;

Section 6.

i I INTERROGATORY ~ NO. 8 )

i Who constructed tests referred to in 6.d and 7.d.

(a) Provide background of company or individual in  ;

test construction. '

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RESPONSE

Operator test construction since the TMI-2 accident has been supervised by M.L. Beers, who was Group Supervisor,

' l Nuclear Operator Training, Metropolitan Edison Company, and by -

Frank Kelly. Mr. Beers' resume is attached. For Mr. Kelly's l background, see response to Interrogatory No. 4. [

Prior to the accident, individuals responsible for test -

construction included Mr. Beers and Mr. R.W. Zechman, Super-  !

visor, Operator Training. Mr. Zechman's qualifications-are attached hereto, i

INTERROGATORY NO. 9 How was reliability of_ tests (6.d) assessed?

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RESPONSE

The tests were constructed in accordance with. accepted industry standards, which Licensee considered to be adequate.

Furthermore, the performance of Unit 1 operators on NRC-admin-istered licensing examinations has been above the national average. This is a significant indication of the reliability of Licensee's testing and training procedures.

INTERROGATORY NO. 10 How will reliability of tests (7. d. ) be assessed?

RESPONSE

These tests will draw upon the OARP and the recommendations of the review committees which are now assessing Licensee's training and testing standards. In addition, operator perform-ance will be analyzed by management on an ongoing basis and ad-justments to course material and testing will be implemented in accordance with this review process.

INTERROGATORY NO. 11 What differences between items requested in.#6 through #10 do you believe will reduce the number of projected incidents upon restart of TMI-l over past performance? Explain.

(a) What is your level of confidence? On what is it based?

(1) Give basis and rationale other than opinion.

Give personnel and consultants involved in any study and their qualifications relative to hiring and job performance evaluation.

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RESPONSE

All of the changes to Licensee's operator training and testing are designed to improve operator capabilities to assure the safe operation of Unit 1. Our confidence that these changes will reduce the number of projected incidents is based on the intensified OARP and testing prior to restart of Unit 1 and on the comprehensive reviews being conducted by special committees of experts in nuclear operations, train-ing and testing.

INTERROGATORY NO. 12 What differences between items requested in #6 through #10 do you believe would have prevented or mitigated the TMI-2 accident? Explain, being specific.

RESPONSE

Testing and operator training in similar incidents at ,

other nuclear plants, small break Loss of Coolant Accidents (LOCA's), other abnormal conditions, High Pressure Injection System and Reactor Coolant Pump operations, and redirected emphasis in heat transfer and fluid dynamics, as described in the Restart Report, Section 6, are to prevent an accident like the TMI-2 accident.  ;

i INTERROGATORY NO. 13 In your experience in operating a nuclear power plant, have i

some individuals performed better than others in " totally unanticipated situations"? (p. 104 Rogovin) l l l l

l (a) Was this true during the TMI-2 accident?  !

I (1) Have you identified such individuals? j (2) Have you identified the characteristics of l those individuals that were effective?

(3) Have you identified characteristics that were not effective? P (4) Provide characteristics referred to in 13.a.

(2) and basis.

(5) Provide characteristics referred to in 13.a. '

(3) and basis.

RESPONSE

Licensee's operators have been selected and trained to have the capability to respond to unanticipated operational ,

situations. Licensee cannot identify any subset of its opera-tors to date who have " performed better than others in totally unanticipated situations". This applies to Licensee's opera-4 tors during the TMI-2 accident. See also, Response to Inter-rogatory No. 14. l INTERROGATORY NO. 14 How do you plan to cope with " totally unanticipated situations"?

(a) Have you provided for these situations in training?

Explain how.

(b) Have you provided for these situations in screen-ing before hiring? Explain how.

RESPONSE

Training programs now include Simulator Training with increased emphasis on unanticipated situations, decision

analysis training, guidance for the operator outside the realm of established procedures, and safety analysis workshops, as listed in the Restart Report, Section 6. Licensee selects applicants with the proper background and experience which, together with subsequent training, will enable them to respond to all operational situations. See Responses to Interroga-tories Nos. 6, 7, and 34.

INTERROGATORY NO. 15 Will there be a " gap" between simulator training and type of plant for TMI-l operators?

(a) If so, what kind of gap or gaps? Describe.

RESPONSE

Licensee's operators are trained on a simulator located at the B&W Training Center, Lynchburg, Va. Since the accident at TMI-2, all of Licensee's operators have been trained in a B&W simulator training module which trains operators based on analysis of the TMI-2 accident, and exposes operators to simulated, unannounced abnormal and emergency plant conditions.

Although control room configuration of the simulator differs from the Unit 1 control room, training in control room manipu-lations is transferrable to the Unit 1 control room.

INTERROGATORY NO. 19 Under proposed redesign of control room, to how many vari-ables must an operator respond?

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(a) During normal operation? r (b) During shutdown operation?

(c) During startup operation?

(d) In the first 10 minutes of a replay of the TMI-2 accident?

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RESPONSE

Section 2 of the Restart Report identifies changes in the control room design for Unit 1. In addition, consultants to Licensee are conducting a human engineering study which is ex-pected to contain recommendations for future control room rede-sign; however, no " proposed redesign" has yet been identified.

Licensee has not, for the various operating modes described in this Interrogatory, quantified the total number of variables to which an operator will be required to respond under the i

current redesign of the control room.

INTERROGATORY NO. 20 Give questions of #19.a-d. for pre-TMI-2 accident control room at TMI-2.

RESPONSE

With respect to the Unit-2 Control Room, a human factors evaluation of control room design and operator performance at TMI-2 was published by the NRC in January 1980 (NUREG/CR-1270, Vo l . ,1 ) . . A description of the controls, displays, integrated controls / displays, and annunciators to which an operator was required to respond are contained in the report. Licensee

has not quantified the total number of variables to which an operator was required to respond in the Unit 2 control room prior to the TMI-2 accident.

INTERROGATORY NO. 20 (sic)

Do you test for visual acuity, color blindness and reaction time for operators and supervisors?

RESPONSE

To qualify as Reactor Operators and Senior Reactor Oper-ators, Individuals are required to be examined by a medical doctor utilizing American National Standard ANS/3.4/ ANSI N546-1976, "American Standard Medical Certification and Monitoring of Personnel Requiring Operator License for Nuclear Power Plants". Testing for visual acuity, color blindness and manual dexterity is included in the examination.

INTERROGATORY NO. 27 Why was 71% considered adequate as a passing score on annual examinations, with no need for " accelerated training program"?

(a) Why do you now believe that 71% is not adequate, or 81% is not adequate? (81% refers to score needed to avoid all training) .

RESPONSE

This interrogatory does not accurately describe Licensee's grading standard with respect to annual requalification tests administered under Licensee's Operator Requalification l

{

Program. For a desc;iption of these standards, see Section 12 i

of the FSAR for Unit 1. These requalification grading stand-i ards have not changed since the TMI-2 accident. The numerical grading standard alone does not indicate the " adequacy" of j the examinations. The construction of the examinations with respect to difficulty is such that the passing grades selected are considered to be adequate to demonstrate an operator's

knowledge for safe operation of the power plant.

INTERROGATORY NO. 28 Do you believe from operating experience that 100% scores on tests proposed are necessary for adequate operator performance?

(a) If not, what % score would be adequate and why?

RESPONSE

. 100% scores are not expected on these examinations as they are designed. Examination grading standards are explained in the Unit 1 FSAR, Section 12, and the Restart Report, Sec-tion 6. See Response to Interrogatory No. 27.

INTERROGATORY NO. 29 What additional classifications of subject matter are included in the new test that were omitted in prior tests?

RESPONSE

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The audit examination (see Response to Interrogatory.

No. 4) for Licensee's operators to be administered prior to -

Unit 1 Restart, will contain a new section on basic heat transfer,

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fluid flow and thermo dynamics. Thereafter, Licensee's annual requalification examinations, and subsequent prelicensing audit exams administered by the Licensee, will cover the subject.

See Responses to Interrogatory Nos. 1 and 2.

INTERROGATORY NO. 30 Are you planning to train operators to cope with any Class 9 scenarios in addition to those of the general classification of the TMI-2 accident?

RESPONSE

See response to Interrogatory No. 14. Training of opera-tors in Licensee's emergency plan implementing procedures is described in the Licensee's emergency plan, which is contained in Section 4 of the Restart Report.

INTERROGATORY NO. 31 Do you believe that the man-machine interface suggested by many of the recent studies will improve operator performance?

i (a) How much do you believe it will reduce incidents?

Give basis.

(b) Would it have prevented initiation of the TMI-2 accident?

(c) Would it have mitigated the errors subsequent in the TMI-2 accident?

RESPONSE

Improvements in the man-machine interface at TMI-1 are described in the Restart Report, Section 2. Included are provisions for ensuring that control room operators have

improved indication of parameters such as PORV position and saturation margin that were important parameters during the TMI-2 accident. Licensee has not quantified the improvement in operation which will result from these modifications.

The TMI-2 accident was dominated by the failure of the pilot-operated relief valve (PORV) to close. Improved indi-cation of the open or closed position of that valve will enhance man-machine interface. This improvement would alert operators to the need promptly to close the block valve before the PORV and thereby terminate any small break LOCA through a stuck-open PORV.

INTERROGATORY NO. 32 Had a man-machine interface study ever been considered by you before the TMI-2 accident?

t (a) When and for what reason?

RESPONSE

The man-machine interface of the Unit 1 control room was considered and appraised in its original design and construc-tion. Mock-ups were erected using facsimiles of the devices to be monitored on the control boards. Through detailed dis-cussion with persons knowledgeable with the plant operatir.g procedures, these devices were then arranged in a logi;al and operable manner. The physical arrangement finally dovised as a result of this consultation between operating and design t

personnel was then transferred to a drawing for use by the control board fabricator.

INTERROGATORY NO. 33 ,

How had human errors been dealt with at TMI-l'and 2? ,

(a) Was this effective?

RESPONSE

Licensee has treated human errors in a manner which it  ;

believes has been effective, including prevention of human error through training programs, correction of human ' error through retraining and, if warranted, through disciplinary measures.

INTERROGATORY NO. 33 (sic)

Are any principles, used in other training procedures of per-formance analagous to the control room, been borrowed in establishing your training procedures? (sic)

RESPONSE

Licensee's Management and Training Department personnel continually communicate with professional organizations, regulatory _ agencies and other utilities'. .Where applicable, useful principles and procedures are incorporated in Licensee's training procedures.

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1 INTERROGATORY NO. 34 What screening of applicants do you do prior to hiring for training? Provide interviews, examinations and tests used 1 in screening.

RESPONSE

A description of Licensee's selection process for reactor operators will be placed in Licensee's Discovery Reading Room.

Your attention is called particularly to section 1 of "Selec-tion Process for Reactor Operators". Copies of an employee ,

job appraisal report form and a pre-employment interview form will also be placed in Discovery Reading Room.  ;

INTERROGATORY NO. 35 Have you considered how employees' "mindset" regarding the safety of nuclear energy has affected their performance.

(a) What are operators told about their responsibility  ;

in protecting the health and safety of the public? ->

Provide copy.

(b) Provide copy of information both written and verbal given to employees relative to the possible hazards of nuclear power generation.

(1) Is any information relative to b. given in a newsletter or newspaper? If so, provide some examples.

(c) Do you agree that the majority of your employees believe that nuclear power generation is very safe?

(d) What information is given to employees about the effects of low-level radiation? Provide copy.

RESPONSE

(a) Licensee has distributed a_ management policy state-l l ment which provides emphasis and designates specific

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command responsibilities for protecting the health and safety of the public. See Restart Report, Sup-1 plement 1, Response to Question 25.

(b) Licensee's General Employee Training Program, which is administered to all employees during initial training and in annual retraining, instructs em-ployees on the risks and health effects of nuclear power generation. A copy of the General Employee Lesson Plan on Basic Health Physics will be placed in Licensee's Discovery Reading Room along with copies of information on radiation risks and ef-fects, which are distributed to each employee during the instruction. Also included will be an example of instructive information included in a daily news-letter published by Licensee and distributed to employees.

(c) No poll of employee opinion regarding this question has been held.

. (d) See b. above.

Respectfully submitted, SHAW, PITTMAN, POTTS & TROWBRIDGE b 5 / /-/

Ge/rgeF. Trowbridge[

Dated: March 31, 1980

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  • ' Attachment __

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Response to~ Interrogatory No. 1

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w.aar1caNucacar Engin aring, Catholic University of 1952 B.E.S.,

of America Electrical Engi..3aring, Catholic Univer4ity

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Manager, Training Projects Mr.

TrainingKupiec Progransis respc,nsible taught by for '.he Basic Academic Project Manager on the current General Physics. He is-Department of Esalth, Ziucation and I;elfare for the contract for the development Quality Assurance / Quality Control Technician.and He has fie baen a Projc-Ot ?:anager for the developmentystems -

of s Training Manuals for PWF. power srations .

Mr.

Kupiec has been pr eviously- involved with programs whi ch are ur.dar develo.nman . bv advanced .

General .vsics Ph and which relate to co.. ncial utility programs He-was a lead investigator on the project to develop an. .

objective Ferry Power operator Plant simuister. perfr.mance method using the rowns B

preparation, materia.3s anc. reviewo rograms.and editing of training textsHe also' assisted i ,

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Westinchou.ne Senior Training Engines: Electri c Cercaration 4

Mr. Kuplec years a: ns a Eenior Trai .ing r.ngin: er for .

rine Training Center.Wettinghouse_I*e:.ric Corpora:, ion .

tion and ir.r,tre: ed i.. -he He d retted on.e: trair,ing engir.yers areas cf .

radiatior and con:rol, pro <r::ior, and nfety,. Fr o:ess instru ner t3 :c,r :heae). and elec:ri;i:; ar.d eiec ronter. 3:.y e sp , a tior, sibilities

.Olar. Prepara: aise10r., in:1 t93: 'iei lesson reo:e wr::,ing . _ 3 cs s., . ,_

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1977 - Presen: General Physics Corperation Manac.er Traininc. Fro.iec ts o

Mr. Ku.c ie c. is'rcs.Onsible for the Basic Academic Training Pro rams tauc.h b.v General Physics. He is Project Manager on the current contract for the Departs.ent of Health, Education and Welfare for the development and field testing of courses for a Nuclear Quality ~Assnrance/ Quality Control Technician. He has been a Project Manager for the development. of Systems Training Manuals for PW?. power stations.

') Mr. Kupie: has been previously involved with advanced-

,' .oroc. rams whi ch are - ur. der develo.cment bv. General Physics and which relate to co.=.ercial utili t.e .oro: rams. .

He was a lead investigator on the p'roject to develop an objective operator perfemance method using the Browns <

Ferry Power Plant ~ simulator. He also assisted in the i preparation, review and editing of training texts, materials and programs.

f, g . .c 1365 - 1977 Westinchouse Electri c Ccrpora tion Senior ,taining s _.ng~neer_

z Mr. Kupiee was a Sanier Trai .ing r.ngin::er for - nine years at ne stinghou st- 'E:er.ric Corpora: ion, Zion Training Center. .He d rerced c:he: :raininc.enginrers and ir.strurted in the art es ef re a c.r theory and cont.rol, radiatior. prote::ior and saf ety , . pr orses instru entario..

and con:rci, <-lec:riri:; and eitetronicr.. His respon-sibilities aise in:1_ dei-locson no:e~ writing, Icts sn

.olar. cre.taratior., test ..: reparatior, and studer.t. eva lua- -

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'rTaile .at the !:ational ?ureau of Scanda:ds; ::r. Edpiec -  !

donducted laboratory es:;,eria.snts of an applied and o .- develop.. ental nature ir: the areas of neutren physics ~,

solid State radiation ditectors, and a' fast neutron

< irradiation facility. The irradiation facility .cas

- to be used for testing and evaluating reactor :naterials .

for better and safer energy production from reactors.

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-SPECIAL QUALI. ICATIONS +

v Mr. Kupiec holds a Professional' Engineer's License in the State of Illinois and'has held a Senior F.eactor Operator's license .at a 10 D: !?uclear Training Reactor-  ;

at the Zion 2:uclear Power Station.

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J. -Attrchment Re:pon d .to Intcrrogntory No. 2 I PERSCMAL FiSU?E

A :E: Cennis J. Bolt:

ADCRESS: Box 1280, R. D. 96 Lcbanon, Pa. I1042 rHCNE: 717-565-6017 . -

DATE OF 81RTH: Noven.be.t 14,'I948 .w .

n HEALT:l: ExccLtent PERSCNAL: 1.farried: Ocpendents - (Cife, Fotut Sus Hei9 itt: 5'8" leeigltt: 165 pounds.

Hobbies: Cauping, Fishing, Uwiting EDUCATION: HRC Senior Openator Licen.se No. SCP-2784-1, Tt.flNS Unit 1 - August 19 78 .

NRC Senior Opci:ator License No. SCP-2 754, TttlHS Unit I - August 1976 NRC Reactor Operato.t Licen.se No. CP-3615, T!.ilHS lhit 1, - August 1974 1.!chtopctitan Edison Conpany Training P.tes.taas See Enctostate I Lebanon Valtcy Cottege Annuitic, PcunayEvania ,

1966 - 1967 Fi.tst Semester (L fo.1: Chemlsb:y - Pre-!fcdical.

High Schoct Gnaduate - 1966 Northc.tn-Lebanan High School .

F. cdtnicksburg, Pcan-sylvania

!L:]c.1: College Pacy. .ttany

il LI TAR' : Ho !ititary Experience r

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' D h "o ]JuuD o o Ju u .; h]lh Inl .m CXVERIENCE: ~ January 1, 1971 to Prc.scM : Empter!cd bij l'ct=peCitan Edisca.

-CTn.;nnyToliG.Qhe pc'sitTon of Adirints.tnate.1 - Nacicar Teciu:ical Trab:ing. I have been itu t~x nMily invctecd in the' deuctopmera and 'impCce:catation cf Three '.N[c !s[1.:d '::scEcar

' Station Uait I and Unit 2 Reactcr *C; :nMor and Scnicr Reactor Openator License Trainbtg Prognarts. Thi.s includes scheduling, instructing, and documentatica of nicsc Ltainb:9 prognams, . as teelt as ute admbthtredian of mock Nuceco Rcgulatory Cciantsslon RO and SRO ticane examinaticas and c.,at exar.Ltaticas. I personatig te.1dc the examination used .in the issuance of tlte orightel TML-2 superelsory NRC SRO Cro.ss Licenses -- the first

. time even. that ti:e NRC graitted operclor ticcuses based on the I tens heavitj involved .

results of an In-hcuse excanination.

in the design, teriting, L aining and implem:MMion of Ste' TMI-2 Radiation Energotct) DniLLs required fo.t the issuance of

.the NRC Stdion Cperating Licatse. I teas perscnally designated t

coordinator fo.1 a prevrous T!.fi-2 Unit Supe. tin.tendent NRC SRO License Training P.tognam, and teas pctsonaltij involved in . senior site managensat L aining programs. Hold cu.trent SRO liccuse.

I activettj paMicipde as Refac. Ling Supervlsc.t in ute annual TML-1 refueling open dions. PaMicpded in Three flite Island -

Nuclear Unit 2 Recovery Effort folto:cbig !.' arch 28, 1979 as As.sistant Site Emergency Coordinator, in char.ge of on and o'ff-site heattit physics and chernhttij operdions. involving dosciutte ;

as.ssssments and sampling activities, and direct supe.tvision of all nadicactive liquid tAan.sfers, clean-up cperations and

~~

nadicactive Liquid retca.ses from TMI Units I and 2.

October 1975 to Januarat 1977: Held position of Ti.ft 1 Openations Sitif t Fo.teman Nuclear. Supervised shift epcndians during 4

plant's .btit.ial f act ctjele and first .tefactb:9 catage.

' October 1969 te Octcber 1975: Held pc',ition of Contnot Rocm Operator - Nuctcar at. Tul- 1. Ccmpleted the attached progrcans' successfulCtj and obtained an NRC RO 'Licensc. Activcitj paMicipated in Tift-1 initial Mart-up and icsting pr.cgnams *

(U> tit tea.s declaren e . mcacial in Sep tec.ber 19 71) .

^

Tcbruatu 1969 to, Getaber '!969: h*cri:cd M :::t Ed's Cnan!and: -

Gencncsing Statten a.s Sconchoom lbtager - c.aiMab:cd inventerics.

~

for each.inertj ecptacewatt parts, chen.icals, rzintenance ap;3c:. Mets, etc. Dutic.s included stacileepbtg, ordering and dispensing of :

materials and paMs.

June 1968 to Febn'uaru 1969: Wor!cd c.s Buite.: Rocm Assis tant M Met Ed's Cra:eford GenerMing Station. .

Februaru 1967 to Ju>te 1968: h*orked 'for nitz:ycr Laboratonics, Inc. as a Chemical Pnocess Reactor Opena.ter. CcMacCf.cd Chemical Rcactors c::; foged in the naitufacture of patented [ives teck medicbtes .

~

, a.

-)-,.,

!.!at 1966 .to Secte::h.

a - e..1 1966:

Er;.y[cycd bij Lebar:cn 1.'e:ca Pubits l:ing C:apny, Lc,o.t;wn, Pc.:n s tjl':aina, c5 a i;C;eo:UP&t p 20f tCad2 t.

D*"]D waN w

  • )'30Y N. ul .o x-

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4 4.

ENCLCSURE' 1 lDiTRCPCLIT,W E01SCN CClSAW SPCMRED TRA!VING 'rTNRR5

1. Tl.f t Rcacio,1 Cpenclor Cettsse - 10/20/69 - 9/19/70 (1) lJa.th ( l20 ftrs )

(2) Classical Physics (40 hu) ,

(3) Atornic Pitysics ( 'O hrs) .

(4) NacLear Pitysics (30 has }

(5) Shielding (40 itu)- _

(6) Ifect Transfcr [30' hrs)

(7) Reacior P!tysics (L20 hu)

(3) Reacior Kinctica (140 hu)

, (9) Reactor Operations (140 hrs)

(10) Health Physics (80 hrs)

(l1) Insettunentaiian and Centrol (50 hrs)

(l2) Nuclear instntenentation (20 itrs)

(13) Basic Elecitonics (40 hu)

(l4) NSSS and Balance of Plant Sys.tems - TlU-1 (S00 hat)' . .

' 2. Post Tncining Paoanan: (600 hu) - 1/11/71 - 4/25/71 Systems and Operating -Pucedures ncvicte.

3. Genotat Efec4 tic Tunhine Course (20 hrs) - 7/71 I Cpena. tor turbinc cott:sc bij Genenat Eicctr.ic

, 4. Reac2cr Fcr.iLiari:atien n

PnOQMaJn (40 h s) - 9/71 Ccnducted at Penn State Universittj Reactor FacitiAy, ' State Coitcge, 'Pa.

included: 1. Nucicar Instrtu;:catatica Experiments

~2. SIictding Expeniwents i 3. Crit.icaC !da',s Expcnie:c'it.s :

7

4. Centncl Rod t' orth Dctchnis:aticas.

. 5. . Fcitt. Stant-ups ch the TRIGA Reacto.1

5. TI.f1-1 Pac- Audit Tna,ining Prooncan (200 hrs) ~- 1/29/73 - 3/2/73 1-Included
Lecitu;c.s cn ,Tli NSSS,-ncspensc/to alc.un procedd:ss, neacto.1 ~

phys'ics, insettunentation and copinot, Integnated Cci: tact V

- System, process . inst 1tur.cntation, Jechnical Specificellons, _

i Cpenating and Cn:engenct ) _ Procedures, clictrical systems,[and.

l_

scLecied NUS(Tape.s.

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Sie.afn.tu.i Onientatic,t Cabue ' (.32 [his ) '- 7/ 73 Conduc.ted by Babcock at:d Wilcox Cong.

7. 755 swti;cd Water Rcactc: Sheutator Tnabtis:a P.:da~::.s Sy Sabcock a,td Wilcox at Ltj ,1chbwtg, l'inginia'

( 50 h,u ) - 5/ 73 (40 h.u) - 1974 .

(40 h.u ) .19 76

. ( :0 h.u ) - 19 78

( 40 h,u ) . - 1979

8. Tl.ft-1 Prc-Liccuse Revicw-Program (l50 hrs 1 - 1974 Conducted by: 1. Babcock and Wilcox^ (90 h.u) i 2. Gcucnai Pitysics Conp. (90 hrs) .
9. Titi-1 Licensed Openator Requalificatien ^ Proanam - 1974 - pacscnt a 10. Tt.fI-1 SRO Liccn.se Trabdatg Proy.an ($0 h,u) - 6/16 4

Ii . Ncs.tinpitotac Electric Conpana.tica AEH Opcrator Training Pror.atn (20 h,ul' - 5/77

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.. e-Att'echment~ V

? Re2ponto to Atttchment No.-2'

_R._E.S U::E

a m : Richard W. ,ec.nman t

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'W}\g y gLg q i

face "jdress: 458 f:. Holly Street Elizabethte.m, Pa.17022 Education:

~~

High School Graduate - 1955 Reading Senige High School

, Reading, Pa.

Pennsylvania State University University Park, Pa.

Accuculated S3 credits (1951 - 1959)

Penn State t:uclesr= Reactor Operator /SRO Training Program - 1965 B&W Unit I Muclear System Progra:: 1959 B&W Unit. II i uclear Systems ?ro; ram _i374 B&W Simulator Star:ru p Certification Program 1977- -

^

Licenses Held: 1) AEC OperatoEs ~ License 0? _1182 Pennsylvania State University 1955 - 1956

  • AEC Senior Operator License 502-750 2)

Penn State University 1956.- 1959'

3) FCC 2nd Class Radio. Telephone Li ense (1954 -to prese>
4) FCC General Class Amateur Padio License (1954- to prest Er aloterent His tory: Ser,terbar 1959 :o crcsent: Erol:.ved 3s" the it-:e trool e i tan Edison Con:pany in 1959 as a Training Specialist. Was responsib,ie :or t. ne ,..u ,cini s tra ti n :r.r i raining c r. t.ne TiII Unit I Oaerator/ Senior "giratcr, Cold ~and Hot License Training Pr. ,r? E. . ,.Particich ted in .hc administration un t'I. _L v;e>

anu, traint:q or....! i c. ,.':t s Personne,i und was promoted to Suparvisor ofEira.nin; on Sapte, Sar i , - ,I ,'J / O .

Sente ber 1953 to Sentec.her 1959: E -icyed by the Pennsylvanic- S ate Universi y :y:ita Engineering Di.t r.tue n t . Ucing cuali fisc a: ' a ' - ^ Licensed .

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S e.n.te.r.S.a.r. .'. .'.5 5 .to,_12 61.: D a l o,,ea d b,' th, !! . ., tc: s n E.lec tric Ccc73ny, i.r,raldale , Pa. as a Scnior E1.ct,enics Tc..nnici3,. i.,> 3 s ,.; 3 - ,, ., s i bl e f' -

C a l 10( ' f. I ' n 0 f ;> rG j a c ;i ,n s (,2 ,' , ;; 'g,3 t ,,3 I'0,6 a ll '/ 2 tJ 0 .:1 r. ;r j,,; ts; d rid Ih C rO,12 '/0 d , , i C O S .

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Att"chment

~

Re::ponT to IntTrrog2t2ry No. 2 iHREE MILE ISLAt:E TRA!:;IM U.s iRUCi.c.a__t_ _3_9_:eg_ _ .

oe a D 3-

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oo o .. 2 EDUCATION llame of School Loca tion Dates Attendad Palc.yra High School Palnyra, Penna. 1961 - 1965 Graduated Colle Frap wi thout Foreign Langu:

Millersville Stz.te Collega Millersvi!!e, Penna. 1955 Did not graduate -

a

. n Major USAF Radio Relay Repairman Keesler AF5 June 1956 - Graduated School Mississippi February 1967 Com unications Electronics Sembach AFB March 1967 - Graduated Correspondence Course Germany April 1967 Radio Pelay Repairmans Sec. bach AFB April 1967 - Graduated Correspondence Course Germany *

. July 1967 - -

Transis tor School Frankfurt, Germany June 1968 - Graduated CREI - Correspondence --- va ri ous --- 196S - 1970 Did not complet because I stopped working c electronic equipmant.

Auxiliary Operator Three Mile Island April 1971 - Graduated Training Middletuwn, Fa. October 1971 Control Room Operator Three Mile Island Parch 1974 - Graduated Training Middletcwn, Pa. & ;ovember 1974 Lynchburg, Va.

US Ins'.ruc tor L'orkshop Rockville, "d. Sectember 1975 - Graduated Sanior Cper stor Training in re e l'i i 7 island J..ne 1976 - Grajuated Mi dd le t;.in , Pi.

i Supervisors Cavelop;:ent Reading, Penna. February 1977 - Graduated Program

'ersonnel "; et ':n t !4h erisb urg , E ni. Jur.a l977 - Gra f .I'.e j

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Experience:

' Ail,inist~rator --I:uclar and Technical Training - P:tr:politan Edison Cc:gany Three Mile Island 1915 - present In this position. I have been responsible for classroom ins'truction of the ,

Operator R2 qualification Program. An additional item has b'een to ir.plement the~

Ralacement Cperator Training Programs forIEsactor Operators and Senior Reactor Operators. The ,iob' duties also included' scheduling and docur.enting training programs, including initial training for TMI - Unit 2. I also participated in TMI - Unit i refueling operations, and periodic control ' room duties, in order

~

to maintain proficiency for my Senior Operator's License, obtained in this ,

posi tion. -

Centrol Room Operator - Nuclear - Metropolitan Edison Company Three _ Mile Island ,

1974 - 1975-

\

In this position I was responsible for the operation of the plant .(TMI -

Unit 1) from initial criticality through the startup program, commercial operation and initial TMI - Unit I refueling. Additionally I was responsible -

for directing the activities of the Auxiliary Operators assigned to the shift.

Obtained Reactor Operator License while in this position.

Auxiliary Operator ' A' - Muclear - Metropolitan Edison Company Three Mile Island - 1970 - 1974 Folic. ting the initial. training' progra:. I ues responsible for operating equipt:ent in the plant as itmas turned o/er fro. the. cons truction cc::gany.

Additionally I participated in- the initial procedure writing effort, Reactor Fuel receipt and initial core l_oading.

I,ju.se F-cuwy lectai r, H: 3,:q , F: . 37C "y job ccesined c f 'skir.ning eci, s:alcir.g i ogs Inc cbs n; 193t scu.v ting.

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Rim.:s .'orm (con tinued, , _ _ iPace 3 of 3-Radio F.ilay Repairiran - USAF 1966 - 1970 This riositien required the maintenance of the micr:. wa 'and rultiplex equip;r.en t. Additionally I was responsible for directing the activities of- the three other repairmen working in the departrent.

' Butcher - f*alvin Burkholder, Campbell town, Pa. 19H - 1966 I worked as a Seef skinner, meat cutter and retail clerk part-time and full time as I learned the trade.

The following items are benefits of my work . experience:

1) Communicaticn ability - this has been enhanced from being an instructor for four years.
2) Admininstration, Docurrentation,. Scheduling & Impler.antation - my duties -

as Administrator - tiuclear and Technical Training have required new .-

ideas to save time & money on documentation procedures and efficient use of instructors and classroom;.

3) Adaptability - In being able.to transfer from an operator to performing-the duties I . presently have as an Adminis trator which requires ' good'-

leadership qualities for directing classroo=' activities and oral examination administration.

Addi ti_onally cy ~ eepicynnt'r '.i.ucq y :.as ad !ed tc the abili$ of -

problem solving wi th 'a miniraum of tima and effort. -

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-4

  • 4

Attrchment N A';K l.. KEl.LY Re0ponse to Interrogatory No. 4

_E K_P_E31_EjC.E, , . i, EE.=5 H.

~

Twenty-five (25) years in the nuclear industry engaged in nuclear power plant starte and test, operator qualification and regulatory evaluation of operator proficiency.

Specific Experience Hiohlichts:

1. liUCLEAR REGULATORY C010:15510?! - Seven (7) years.

Chief, Operator Licensing' Branch. Responsible for the formulation and evalua-tion of operator and senior operator examinations, administered to operators of power, test and research facilities. Developed and implemented tiRC policies for the use of nuclear power plant simulators utilized as training devices.

2 OPEPATOR & SEllIOR OPERATOR QUALIFICATI0?l & EVALUATIO?i - Ten (10) years.

Directed efforts and participated in the selection, training and evaluation of

. operators while in supervisory positions with Uestinghouse Electric Corporation

.and two (2) nuclear service consulting finns.

3 P.ANAGEliEllT OF tiUCLEAR POWER PLAtiT TRAI?illiG SI!iULATOR - Three (3) years.

Responsible for the startup and operation of the ' festinghcuse !!uclear Training,

. Center, Zion, Illinois , US A. -

4 STARTUP & OPEP.ATIO!i 0F fiUCLEAR POWER PLA!iTS - Five (5) years.

Responsible for the startup and operation of nuclear power plants, test reactors and,research facilities - tiRC licensed on six (6) plants.

EDUCATIOff -

o BS Electrical Engineering, University of Vermont -

o Completed credits for $5 fluclear Engineering, University of' Pittsburgh REGISTPATIONS /LI CEtiS ES fluclear Engineer, State of California, Registration !NU383 '

PROFESSIONAL AFFILI ATIONS ,

Ancrican fiuclear Society - Past Chairman, Reactor Operations Division CC!'.'il TTE ES / AD'/150P.Y GROUPS Present Secretary, ANS-3, Subcommittee on Reactor Operations (authors of ANS Standards fi18.7, N18.1 and A!iS 3.5). -

ASF.E. Opera tions and l'aintenance Com .ittee ,

Att chment e; 48 *-

(

Re:ponOS to Int 2rroga.tcry No. 8

.niG Oy. M Ste:E-0F' .n 3 n i::s 2.D . , .D v5

!"'M A1.L L. SEF.RS L'i'aNM , PA. 1/042

~

E * g.. ',0.N r j l 7/73 to Prccent: Metropolitan Edison'Cer.pany Three Mile Island !*uclear Station Group Supervisor - Technical Training .- Nuc1 car 6//3 - 6/73: Metropolitan Edicon Cocpany Three Mile Island *uclear. Station Shift Supervisor 11/70 - 5/13: Metropolitan Edison Cc:pany Three Mile Island Nuclear Station Unit II Shift Forenan Unit I Shift Foreman 1966 - 1970: Westinghouse Electric Corporation Naval Reactors Facility Idaho Falls, Idaho' Reactor Engineer ., , ,

1961 - 1966: Westinghouse Electric Corporation Naval Reactors Facility .

j Idaho Falls, Idaho d

Reactor Test Technician 1956 - 1961: Westinghouse Electric Corporation Bettis Lab Pittsburgh, Pa.

Electronics Technician  :

EDUCATION High School: Dayton IIigh School, Dayton, Pa.

Graduated 1946 College: Pennsylvania State' University 1946 - 1947 1-Acadenic Year Electrical ~ Engineering-Course of Study Other: Allegheny Technical Institute Pittsburgh, Pa.

Evening School 1954 - 1957.

. Industrial Electronics-Course of Study.

Company Sponsored Courses:

Rabcock 6 .Uilcor. P':R- T.echnolegy Course

.' .Eailey_ Meter Cc.mpany.-LIntegrated Control System Familiar'izativn

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.19 50 '-( st 952 U.S. Arny --Tufantry Trivate to St cCf k.neany .

Sbived in brea with Inst position as Plateen Forgaant -

!cnorabic, Discharge-

pbe.::.f.L.-
=.:-

Z i r d ' i t.e : 1/31/23 Dayton, Pa. Height: :5'9" Weight: 165 lbs.

Sh r i. d : Wife - Graduate of ?cun S, tate Calversity

_pc: i Id : .:n : Five; ages - 28, 25, 23,- 19,-13

" alth:

, Exec 11entr- No-physical' limitations.

E:%ies: Flying _- Private Pilot, Tennis', Skiing

..LI._GN._S_E. S R;D - QUALIF ICATIONS

- 1966.. Qualified Reactor Operator - ALU Dual Plant Prctotype 1974- Three Mile Island Uait I NRC Operator Licence OP-3473 . .-

- 1974 Three Mile Island Unit I NRC Senior Operator License S0P--2224 1976 Three Mile Island Unit I

. Reacval - NRC Senior Operator License SOP-2224-1

..1977 . Three Mile Island Units 1 & II A::: ended - NRC Senior Cperator License SOP-2224-2 1973 Three Mile Island Units I & II Ronctal - T.RC Senior Operator License SOP-2224-3 4 .

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_.i_-

  • A S haw, PITTMAN, PoTTs & TROWB RIDG E 1800 M STR E CT. N. W.

WA SHINGTON, D. C. 20036 RAMSay O.POTTS sTCPMEN S. MuTTLER (2021331- AiOO STEuART L. PsTTM AN wsNTHROP N. SRowN _

G EORGE F. TsowSmaOG C J A M E S W. M A M ' "I STEPMEN O. POTTS ROBERT E. 2A..6CR TCLCCCPIER GC AALO CMARNOFF RICH ARO C. Q ALEN PMcLLip D. SOSTwsCR ROBERT 3. ROS SIN S (202)296-0694 & 296 1760

m. TIMOTM Y M AN LO N STEVEN M. LUCAS -

G CORG E M. ROG ERS. JR. M ATI AS F. TRaviESO OiAZ JOHN S. RMIN CLAN OCR VICTORIA J. PERMINS TELEX EAUCC w. CHURCMtLL JOM N M. O'N EILL. J R.

LCl LIC A. NICMOLSON. JR. JAY A. EPSTIEN 89 2683 (SMAwLAw wSM)

M ARTIN O. K RALL RANO L. ALLEN KtCM AND J. K ENOALL TIMOTMY 5. MeSRIOC CASLC"SMAwLAw" J AY C. S'LS ERG CLISASCTM M. PENOLETON l'.A'I S A R A M. ROS SOTTt LUCY G. CLIASOF GCORGE V. ALLEN JR. PAU L A. M APLAN COWARD S. CROSLAND wM. SR ACFORO REYNOLOS MARRY M. GLAS SSIEG EL COUNSEL FKCO A. LITTLC TMOM AS M. McCORMICM FKED ORASNCR SUSAN O. FALMSON MATM ANI CL P. S R E ED. JR. w lLLI AM P.SARR MARM AUG E N S LIC K JOHN L.CARR.JR.

CEN C ST L. S LAKE. J R. PMcLe p J. MARvgY CARLETON S. JON ES ROSCRT M. GOROCN THOMAS A. SAXTER J CAN N C A. CALD ERON JAM ES M. SUROCR S AR G AR A J. MORG EN

  • S MCLOON J. WEISCL SONNIC S. GOTTLIES JCMN A. MeCULLouGM ALFRCO M. POSTELL J. f ATRICK MICM CY SCTM M. MOOG AssAN JAMCS TMOMAS LENHART S M CILA C.McCAFFERTY STEVEN L. M CLTZ ER O CLIS SA A. RIDGWAY DEAN O. AULaCN *t EN N CTM J. M AUTM AN JOHN ENGEL DAVIO (AWRENCC MILLER

. G, .. .m o ,M o. c. March 31, 1980 Ms. Marjorie M. Aamodt R.D. 5 Coatesville, Pennsylvania 19320 Re: Three Mile Island Unit 1 Docket No. 50-289 (Restart)

Dear Ms. Aamodt:

I enclose Licensee's responses to your fourth (sic; fifth) set of interrogatories. Copies of signed affidavits for these responses are not enclosed, but will be forwarded soon.

Sin rely yours, e

,udL F. Trowbridge Enclosure cc: Service List t